ML20090D831

AO-50-219/75-02:on 750206,approx 4,000 Gallons of Condensate Inadvertently Released to Discharge Canal in Uncontrolled Manner During Flooding of Hotwell of B Condenser to Search for Tube Leaks in North & South Water Boxes

ML20090D831
Person / Time
Site:	Oyster Creek
Issue date:	02/13/1975
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	Giambusso A Office of Nuclear Reactor Regulation
References
AO-50-219-75-02, NUDOCS 8303020450
Download: ML20090D831 (5)

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Jersey Central Power & Light Company ,G(,

MADISON AVENUE AT PUNCH BOWL ROAD

• MORRISTOWN, N.J.07960

• 201-539-6111 unusum e res General ((] Petic Ut Sties Corporation sysism February 13, 1975 e e tu

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Director, Division of Reactor Licensing Office of Nuclear Reactor Regulation

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United States Nuclear Regulatory Commission s I'W, \ v',-

Washington, D. C. 20545

Subject:

Oyster Creek Station Dvdui Nv.30-219 Abnormal Occurrence Report No. 50-219/75-2 The purpose of this letter is to forward to you the attached Abnormal Occurrence Report in compliance with paragraph 6.6.2.a of the Technical Specifications.

Enclosed are forty copics of this submittal.

Very truly yours,

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Donald A. Ross Manager, Generating Stations-Nuclear es Enclosures cc: Mr. J. P. O'Reilly, Director Office of Inspection and Enforcement, Region 1 04W r 1715 8303020450 750213 PDR ADOCK 05000219 S PDR COPY SENT REGION

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, Jersey Central Power & Light. Company (

MADISON AVENUE AT PUNCH BOWL ROAD

• MORRISTOWN, N.J. 07960

• 201-539-6111

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0YSTER CREEK NUCLEAR GENERATING STAIION

. FORKED RIVER, NEW JERSEY 08731 Abnormal Occurrence Report No. 50-219/75-2 Report Date February 13, 1975 Occurrence Date ,

February 6, 1975 Identification of Occurrence Violation of the Tecimical Specifications. Approximately 4,000 gallons of condensate was inadvertently released to the discharge canal in an uncontrolled manner. This event is considered to be an abnormal occurrence as defined in the Technical Specifications, paragraph 1.15C.

Conditions Prior to Occurrence Reactor mode switch in refucI position with reactor coolant temperature approx-imately 150*F.

Description of Occurrence

! On February 5,1975, at approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, the hotwell of "B" condensor was flooded in order to scarch for tube Icaks in the north and south water boxes. As part of this operation, it is required to drain the water boxes in

. preparation for personnel access. This is accomplished by " cracking the back- -

l wash discharge valves (onc per water box) and opening the water box vent valves.

The backwash discharge valves were not returned to the closed position prior to

! ' flooding the hotwells. Because of the unexpected magnitude of tube Icakage, the condensate in the hotwell flowed into the water boxes and out the backwash valves to the dischargo tunnel at an estimated rate of 3 gpm. This condition existed until approximately 0930 on the following day, at which time maintenance personnel entered the north side water box to scarch for tube leaks. They plugged approximately 33 Icaking tubes which reduced the leakage rate to approxi-mately 1 gpm. The observed Icakage rate in the south side water box was very small i

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• Abnormal Occurrence Report No. 50-219/75-2 Page 2 and did not contribute significantly to the release. The release to the dis-charge tunnel continued at this rate until 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> at which time the significance of the event was realized, and the backwash discharge valves were closed. Water sampics were immediately collected from the intake and discharge structure, dis-charge canal prior to dilution with Oyster Creek, and discharge canal after dilution with Oyster Creek at the Route 9 bridge.

In addition, samples of condensate were analy cd from:

1) Condensate pump discharge (water from "A" and "C" condenser hotwells)

2) North side of "B" condenser hotwell

3) South side of "B" condenser hotwell The highest radionuclide concentrations found in the south side of the "B" hotwell were used for the release estimates in Attachment 1. Attachment II shows results of isotopic analyses of the discharge canal water performed by the environmental sample analysis vendor.

There were two service water pumps, each with a capacity of 6,000 gpm, in service throughout the release providing dilution flow. One pump discharges into the circulating water discharge tunnel, the other pump discharges into the canal between the discharge structure and the Route 9 bridge.

Apparent Cause of Occurrence Plant operating procedures did not preclude this specific occurrence.

Analysis of Occurrence Calculations and analysis results shown in Attachments I and II demonstrate that the concentrations of effluents released from the site were less than the MPC given in Appendix B, Table II, Column 2 of 10CFR20 and Notes 1 through 5 thereto.

Corrective Action The backwash di charge valves were closed and the water remaining in the water boxes was pumped to the radwaste facility. Following the collection of canal samples, a dilution pump was started to flush the discharge canal. Revisions will be made to plant operating procedures to prevent a recurrence of this type violation.

Failure Data Not applicable.

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, ATTACll MENT I s'

Release Calculations Based on Condensate Analysis from "B" Ilotwell South Side Sampled February 7, 1975 at 2000 Discharge l Maximum 2 Tunnel Canal Conc. Conc. Conc. MPC (pCi) (pCi) (uCi) pCi Cone.+

Isotope ( m1_[ (ral) (mi) ml 10CFR20 Limit 3 Il31 4.4 X 10 4 2.2 X 10 7 1.1 X 10 7 3 X 10 7 .37 1 133 3 X 10 5 1.5 X 10 8 7.5 X 10 9 1 X 10 6 .0075 Xel33 2.35 X 10 4 - - - -

Xc135 2 X 10 6 _ _ _ _

Ba140 3.5 X 10 5 1.75 X 10 8 8.75 X 10 9 3 X 10 5 .0003 La140 4.1 X 10 5 2.05 X 10 8 1.03 X 10 8 2 X 10 5 .0005 E = 3. 35 X 10-4 E= 378 I Assumes 6,000 gpm flow and 3 gpm Icak; exclusive of nobic gas and strontium (concentration calculated in discharge tunnel).

' Assumes 12,000 gpm flow (from two service water pumps) and neg1ceting dilution in discharge canal volume.

3 Reconcentration factor not used; based on maximum possible canal concentration.

Volume = 22.5 hr. X 00 X a g/ min = 4.05 X 10 3gal Activity = 4.05 X 10 3gal. X 3785 cc X 3.35 X 10-4 = 5.13 X 103 pCi gal.

Canal Concentration (max.) = 37.8% of 10CFR20 Limit t

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